Level energy(keV)   Spin & Parity       
       ground state      1/2-                  
       5.98200E+01       7/2+                  
Mass (The Ame2012 atomic mass evaluation (II) by M.Wang, G.Audi, A.H.Wapstra, F.G.Kondev, M.MacCormick, X.Xu, and B.Pfeiffer Chinese Physics C36 p. 1603-2014, December 2012)
     110.905295923 ± 0.000001634 (amu)  [mass excess = -88216.279 ± 1.523 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
     1036.800 ± 1.414 (keV) 
Strong Gamma-rays from Decay of Ag-111 (Compiled from ENSDF as of March 2011)
  [ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
   γ-ray energy(keV)  Intensity(%)  Decay mode 
         59.77            0.53         IT 
        171.28            0.09         B- 
        245.4             0.37         B- 
        620.1             0.09         B- 
         96.75            0.12         B- 
        245.40            1.33         B- 
        342.13            6.68         B- 
     *: relative, ~ approximate, ? calculated or estimatted 
     >: greater than or equal to, <: less than or equal to  
  [ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
     Decay mode     Half-life 
       B-           7.45 D 1         
       B-           64.8 S 8         
       IT           64.8 S 8         
Cross Sections (taken from JENDL-4.0)
     Table of cross sections, Ag-111.
     Figures of cross sections, Ag-111:  type-1:  type-2:  type-3.
       type-1: total, elastic and inelastic scattering, capture and fision cross sections
       type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
       type-3: threshold reaction cross sections
Evaluated Data Libraries
     Links to the libraries. 

Parent Nuclides by Reactions in JENDL-4.0
     Ag-110 (Z= 47, A=110), MT=102 (n,γ)
     Ag-111 (Z= 47, A=111), MT=  2 (Elastic scattering)
     Ag-111 (Z= 47, A=111), MT=  4 (Inelastic scattering)
     Cd-111 (Z= 48, A=111), MT=103 (n,p)
     Cd-112 (Z= 48, A=112), MT= 28 (n,np)
     Cd-112 (Z= 48, A=112), MT=104 (n,d)
     Cd-113 (Z= 48, A=113), MT= 32 (n,nd)
     Cd-113 (Z= 48, A=113), MT=105 (n,t)
     In-113 (Z= 49, A=113), MT=106 (n,3He)
     In-115 (Z= 49, A=115), MT= 22 (n,nα)

Fission Yields for Fission Products in JENDL-4.0 Fission Yield Data

   - Neutron-induced Fission Yields (from main actinide nuclides) - Independent Fission Yield -
     Product  Nuclide  Energy   Fission Yield  Uncertainty(1σ)
     Ag-111    U-235   Thermal   1.264150e-12   8.090550e-13 
     Ag-111    U-235   Fast      2.823810e-12   1.807230e-12 
     Ag-111    U-235   High      4.927820e-08   3.153810e-08 
     Ag-111    U-238   High      1.172450e-09   7.503650e-10 
     Ag-111   Pu-239   High      3.189100e-06   2.041020e-06 
     Ag-111m   U-235   Thermal   8.240710e-12   5.274060e-12 
     Ag-111m   U-235   Fast      2.110680e-11   1.350840e-11 
     Ag-111m   U-235   High      5.906990e-07   3.780470e-07 
     Ag-111m   U-238   Fast      2.929330e-14   1.874770e-14 
     Ag-111m   U-238   High      1.405420e-08   8.994650e-09 
     Ag-111m  Pu-239   Thermal   2.834640e-14   1.814170e-14 
     Ag-111m  Pu-239   Fast      3.377510e-14   2.161610e-14 
     Ag-111m  Pu-239   High      3.822780e-05   2.446580e-05 
     Ag-111m  Pu-241   Fast      9.342170e-15   5.978990e-15 
    Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
   - Neutron-induced Fission Yields (from main actinide nuclides) - Cumulative Fission Yield -
     Product  Nuclide  Energy   Fission Yield  Uncertainty(1σ)
     Ag-111    U-235   Thermal   1.712450e-04   7.401970e-06 
     Ag-111    U-235   Fast      4.176640e-04   1.370970e-05 
     Ag-111    U-235   High      1.066480e-02   3.161200e-04 
     Ag-111    U-238   Fast      6.871470e-04   2.287850e-05 
     Ag-111    U-238   High      9.733890e-03   3.194220e-04 
     Ag-111   Pu-239   Thermal   2.936640e-03   1.444360e-05 
     Ag-111   Pu-239   Fast      3.542140e-03   1.734240e-05 
     Ag-111   Pu-239   High      1.535400e-02   1.236300e-03 
     Ag-111   Pu-241   Thermal   5.801900e-03   3.577070e-05 
     Ag-111   Pu-241   Fast      6.387660e-03   3.897680e-05 
     Ag-111m   U-235   Thermal   1.712350e-04   1.911940e-05 
     Ag-111m   U-235   Fast      4.176380e-04   3.418060e-05 
     Ag-111m   U-235   High      1.065990e-02   1.178750e-03 
     Ag-111m   U-238   Fast      6.871130e-04   5.993620e-05 
     Ag-111m   U-238   High      9.732970e-03   7.965190e-04 
     Ag-111m  Pu-239   Thermal   2.936480e-03   2.350710e-04 
     Ag-111m  Pu-239   Fast      3.541950e-03   2.126550e-04 
     Ag-111m  Pu-239   High      1.529780e-02   3.513580e-03 
     Ag-111m  Pu-241   Thermal   5.801610e-03   1.079780e-05 
     Ag-111m  Pu-241   Fast      6.387340e-03   2.047660e-03 
    Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
      → Neutron-induced and Spontaneous Fission Yields of all nuclides in JENDL-4.0 Fission Yield Data